Study on the effect of long-term high temperature irradiation on TRISO fuel

被引：2

作者：

Shaimerdenov, Asset ^{[1
,3
]}

Gizatulin, Shamil ^{[1
]}

Dyussambayev, Daulet ^{[1
]}

Askerbekov, Saulet ^{[1
,3
]}

Ueta, Shohei ^{[2
]}

Aihara, Jun ^{[2
]}

Shibata, Taiju ^{[2
]}

Sakaba, Nariaki ^{[2
]}

机构：

[1] Inst Nucl Phys, 1 Ibragimov Str, Alma Ata 050032, Kazakhstan

[2] Japan Atom Energy Agcy, 4002 Narita Cho, Higashiibaraki, Ibaraki 3111393, Japan

[3] Al Farabi Kazakh Natl Univ, 71 Al Farabi Av, Alma Ata 050040, Kazakhstan

来源：

NUCLEAR ENGINEERING AND TECHNOLOGY | 2022年 / 54卷 / 08期

关键词：

TRISO; WWR-K; Graphite matrix; High burnup; Fuel integrity; COATED PARTICLE FUEL; REACTOR; PERFORMANCE; HYDROGEN; US;

D O I：

10.1016/j.net.2022.02.026

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

In the core of the WWR-K reactor, a long-term irradiation of tristructural isotopic (TRISO)-coated fuel particles (CFPs) with a UO2 kernel was carried out under high-temperature gas-cooled reactor (HTGR)like operating conditions. The temperature of this TRISO fuel during irradiation varied in the range of 950 -1100 ??C. A fission per initial metal atom (FIMA) of uranium burnup of 9.9% was reached. The release of gaseous fission products was measured in-pile. The release-to-birth ratio (R/B) for the fission product isotopes was calculated. Aspects of fuel safety while achieving deep fuel burnup are important and relevant, including maintaining the integrity of the fuel coatings. The main mechanisms of fuel failure are kernel migration, silicon carbide corrosion by palladium, and gas pressure increase inside the CFP. The formation of gaseous fission products and carbon monoxide leads to an increase in the internal pressure in the CFP, which is a dominant failure mechanism of the coatings under this level of burnup. Irradiated fuel compacts were subjected to electric dissociation to isolate the CFPs from the fuel compacts. In addition, nondestructive methods, such as X-ray radiography and gamma spectrometry, were used. The predicted R/B ratio was evaluated using the fission gas release model developed in the high-temperature test reactor (HTTR) project. In the model, both the through-coatings of failed CFPs and as-fabricated uranium contamination were assumed to be sources of the fission gas. The obtained R/B ratio for gaseous fission products allows the finalization and validation of the model for the release of fission products from the CFPs and fuel compacts. The success of the integrity of TRISO fuel irradiated at approximately 9.9% FIMA was demonstrated. A low fuel failure fraction and R/B ratios indicated good performance and reliability of the studied TRISO fuel. ?? 2022 Korean Nuclear Society, Published by Elsevier Korea LLC. All rights reserved. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).

引用

页码：2792 / 2800

页数：9

共 39 条

[21]

Petti DA, 2012, COMPREHENSIVE NUCLEAR MATERIALS, VOL 3: ADVANCED FUELS/FUEL CLADDING/NUCLEAR FUEL PERFORMANCE MODELING AND SIMULATION, P151

[22] Key differences in the fabrication, irradiation and high temperature accident testing of US and German TRISO-coated particle fuel, and their implications on fuel performance [J].